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  • image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
    Authors: Casamor Vidal, Max; Avramova, Maria; Reventós Puigjaner, Francesc Josep; Freixa Terradas, Jordi;

    Several TH-TH code coupling methods are used in the nuclear industry to model the core thermal–hydraulic conditions and the system behaviour. In some cases, the boundary conditions obtained by system codes are applied to sub-channel codes by table (off-line coupling). Even though this approach is in general considered valid, some boundary parameters will present inconsistencies. Alternatively, system and sub-channel codes are coupled using different coupling methods (semi-implicit coupling). Recent studies have shown a strong influence of the bound- ary conditions uncertainty on the sub-channel code results. The present study aims to evaluate the differences produced by the coupling methods by performing a best-estimate plus uncertainties (BEPU) comparison to the following cases: a complete loss of forced flow and a pressurizer relief valve opening. Results show that BEPU analysis presents good agreement with some discrepancies that can be explained and correlated to the boundary conditions deviations between codes. Peer Reviewed

    image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao UPCommons. Portal de...arrow_drop_down
    image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
    image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
    Annals of Nuclear Energy
    Article . 2022 . Peer-reviewed
    License: Elsevier TDM
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      image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao UPCommons. Portal de...arrow_drop_down
      image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
      image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
      Annals of Nuclear Energy
      Article . 2022 . Peer-reviewed
      License: Elsevier TDM
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  • image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
    Authors: John J. Laureto; Joshua M. Pearce;

    International audience; Quantification of nuclear liability insurance is difficult without arbitrary liability caps; however, post-mortem calculations can be used to calculate insurance costs. This study analyzes the Fukushima (Daiichi) nuclear power plant disaster to quantify the cost per unit electricity ($/kWh) of nuclear energy from the lifetime of the plant after accounting for the true cost of the liability needed to cover the damages from the nuclear disaster determined from news reports. These costs are then compared to the cost of electricity currently paid by Japanese consumers, and then are aggregated to determine the indirect subsidy for nuclear power providers in both Japan and the USA. The results show that the reported costs of the Fukushima nuclear disaster are $20–525 billion, which results in a real insurance cost from the lifetime of electricity produced at the plants between $0.22–5.78/kWh. These values are far higher than the current insurance costs by Japanese law of $0.01/kWh and even the total costs consumers pay for electricity. Although the spread in the input costs is large and the reported metrics are incomplete, the nuclear insurance subsidy is clearly substantial in Japan and in the USA. Ideally, energy sources should be economically sustainable without the need for a government insurance subsidy. For the electricity market to function effectively and efficiently in all other countries using nuclear power, the insurance costs should be reported accurately and included in nuclear electricity costs without arbitrary government liability caps.

    image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ Sustainabilityarrow_drop_down
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    Sustainability
    Other literature type . Article . 2016 . Peer-reviewed
    License: CC BY
    image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
    Sustainability
    Article . 2016
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    image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
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      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ Sustainabilityarrow_drop_down
      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
      Sustainability
      Other literature type . Article . 2016 . Peer-reviewed
      License: CC BY
      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
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      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
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      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
      Sustainability
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  • image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
    Authors: Torné Capilla, Eduard;

    En 2019 la energía nuclear fue la segunda fuente de generación de energía eléctrica en España con un 22,6% de la producción. La energía nuclear se produce mediante una reacción nuclear que a su vez genera materiales radiactivos, y es de alta importancia estudiar la seguridad de todos los elementos y procesos que intervienen, para evitar que dichos materiales radiactivos puedan afectar al medio ambiente. Una de las metodologías utilizadas para mejorar la seguridad de operaciones es el Análisis Probabilista de Seguridad (APS), a fin de identificar secuencias de accidentes que puedan afectar negativamente y estimar su frecuencia de ocurrencia para minimizar el riesgo. En las centrales nucleares es tan importante el APS realizado con frecuencia, cómo el contraste de los resultados obtenidos y los proporcionados por Bases de Datos Genéricas (BDG) de referencia, en este caso la española. En este trabajo se compararán los valores del parámetro de fiabilidad de ambas bases de datos, la propia de la central nuclear estudiada y la genérica española, con objetivo de identificar y justificar las diferencias más significativas. Debido a la gran diversidad de elementos presente en una central nuclear, y el gran alcance del APS, se realiza inicialmente un estudio entorno a la metodología APS. De este modo, se podrán comprobar los valores de la central a partir de la metodología APS utilizada, así como los tratamientos, distribuciones y agrupaciones utilizadas en cada caso a partir de los criterios que se definen en función del modo de operación. Una vez revisados los valores numéricos se analizarán todos los fallos de cada grupo, ya que son los responsables de aumentar o disminuir el valor del parámetro de fiabilidad o probabilidad de fallo. El criterio utilizado para evaluar si el fallo pertenece al grupo asociado son los límites de fallo en función de cada componente y del modo de trabajo. Se buscan fallos clasificados en componentes con causas externas a éste, modificando su valor de fiabilidad. A la vez, se clasifican las causas de fallo más comunes para grupos con muchos fallos. Una vez identificados los casos a reclasificar, se calculan de nuevo los valores del parámetro de fiabilidad. A partir de los valores de fiabilidad iniciales y los modificados, se estudian cuáles son los componentes con mayor divergencia respecto la Base de Datos Genérica, buscando casos representativos para proponer su revisión. Se profundiza para identificar elementos en modos de trabajo concretos. Finalmente se relacionan las observaciones realizadas durante el análisis de los fallos y los grupos con mayor divergencia a la base de datos genérica para justificar sus diferencias. Es posible realizar el proyecto gracias al convenio de investigación entre una central nuclear y la Sección de Ingeniería Nuclear de la Universidad Politécnica de Cataluña (UPC).

    image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ Recolector de Cienci...arrow_drop_down
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    image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
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      image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ Recolector de Cienci...arrow_drop_down
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      image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
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  • image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
    Authors: Elgezabal Garmendia, Imanol;
    image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/ Recolector de Cienci...arrow_drop_down
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    image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
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      image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
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  • image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
    Authors: Albaladejo Castelló, Eduard;

    This project is based on the revision and update proposal of document PA.IV.202 Rev.2 “Calculation Manual of the Performance Indicator of Mitigation Systems (MSPI)”. This document is used by the Spanish Nuclear Safety Council (CSN) to verify the performance indicators of nuclear power plants within the framework of the Integrated Plant Supervision System (SISC). This CSN procedure is regularly updated to include news and / or changes in its procedures. During the project, an exhaustive search was made for the changes or new interpretations that have appeared in the meetings of the Reactor Oversight Process (ROP) of the American nuclear regulator Nuclear Regulatory Commission (NRC). In accordance with these periodic meetings, news and changes are published in the regulations of NEI 99-02 Rev. 7, which is the document accepted by the US regulator as a guide for calculating the operating indicators of American nuclear power plants and that it is the basic information for the update of PA.IV.202. On the other hand, the frequently asked questions(FAQs) relevant to the MSPI indicator from plant licensees to the NRC have been compiled. These are issues raised to the regulator due to events that have occurred in nuclear power plants that call into question some aspects of the guidelines, such as the calculation procedure for an indicator. Therefore, through these frequently asked questions, procedures improvements or changes to NEI 99-02 are proposed to correct potential errors that the NRC has to approve before implementation. Subsequently, the FAQs are incorporated into document NEI-99-02. Once all the necessary information from NEI 99-02, the ROP meetings and the FAQs have been collected, a list has been made with all the news and changes relevant to the MSPI indicator. In addition, information has been included regarding the history of nuclear energy in Spain, regulations used by the CSN and on the SISC. Finally, the changes from the previously listed American case have been transferred to the Spanish case. The relevant changes for the MSPI indicator have been selected and adapted to update PA.IV.202 Rev.2 by rewriting its procedures. Also, it is important to say that the procedures have been updated in Spanish since it is a Spanish document. Therefore, the practical part of this project (tables 4, 5 and 6 in section 6) are written in the same language as PA.IV.202 Rev. 2.

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  • Authors: Finon, Dominique;

    In this paper we analyze the recent propositions to reorganize the French industry of reactors in view to increase its efficiency on the export markets. Based on a critic of the choices of reactor technologies offered to export market, the Roussely report published on June 2010 recommends to crown the French electricity utility as the leader of a so-called "French team" and to let him free to negotiate the sale of reactor of any technology that it would prefer as a Gen-2 reactor for example, and to place the French nuclear reactor constructor in a position of sub-contractor. The government has not followed this recommendation rightly. Based on an analysis of the changing world market of reactors, we defuse the criticism addressed to Areva on his choice, as well as the recommendation to open the present catalog of reactors to other models. The analysis leads to underline the importance of Areva's technological and industrial resources and the limited advantages of the EDF's skills in matter of architect-engineering and nuclear operation for winning export contracts. At the end of the day the mercantile approach which motivates the promoters of this tentative reform for competing with entrants prosing low cost nuclear reactors has been disapproved by the government, and that before the Fukushima accidents. We conclude by observing that only a flexible coordination between French industrial players would be useful for improving export performances of the French nuclear industry. On analyse ici les propositions récentes de réorganisation de l'industrie française des réacteurs en vue d'accroître son efficacité à l'exportation. A partir d'une critique des choix de technologies offerts à l'export, le rapport Roussely recommandait de placer l'électricien national en chef de file libre de négocier la vente des réacteurs de son choix (dont des réacteurs Gen2) et de faire du constructeur français le sous-traitant du premier. Le gouvernement n'a pas suivi ces recommandations à juste titre. A partir d'une analyse du marché mondial des réacteurs en mutation, on relativise les critiques adressées à Areva sur ses choix ainsi que l'intérêt d'élargir le catalogue de réacteurs. Cette analyse permet de souligner l'importance des ressources technologiques et industrielles d'Areva dans la concurrence et l'avantage tout relatif des compétences d'architecte-ensemblier et d'exploitant de l'électricien national dans la conquête de marché à l'exportation. Au bout du compte, la démarche mercantile qui motivait les promoteurs de cette réforme en ambitionnant de concurrencer les entrants avec du nucléaire low cost a été désavouée par le gouvernement et ce avant même l'accident de Fukushima. Un peu plus de coordination à l'export serait juste nécessaire.

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    Authors: Paul W., Thurner; Brouard, Sylvain; Martin, Dolezal; Guinaudeau, Isabelle; +2 Authors

    This chapter provides an account of the contestation of nuclear energy in Western Europe and beyond. It presents a new compilation of comparative public opinion data on nuclear energy, original data on protest behaviour directed against nuclear energy, and a systematic account of the development of Green parties. The focus is on the covariation of these factors with the behaviour of the established political parties and system properties (Kitschelt’s ‘openness’). The main function of the chapter is to show the relative strength of the ‘natural enemies’ of nuclear energy—concerned citizens, protest movements, and Green parties—in the countries covered by case studies (and beyond, where possible) and to understand how they interact. The chapter argues that neither public opinion critical to nuclear energy nor sizeable protest behaviour is sufficient to introduce anti-nuclear policy change.

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    Oskar Bordeaux
    Part of book or chapter of book . 2017
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    Authors: Mendoza Sancho, Victor;

    El presente trabajo final de máster se realiza con objeto de establecer una guía técnica en la Asociación Nuclear Ascó - Vandellós II, AIE para llevar a cabo la calificación sísmica de equipos y componentes relacionados con la seguridad, de categoría sísmica 1, en cumplimiento con las bases de licencia de las centrales nucleares (CCNN) de Ascó y Vandellós II. La calificación sísmica se desarrolla en base a requisitos normativos de distinto nivel, de ámbito nacional e internacional, a aplicar en instalaciones nucleares, donde destaca la Instrucción de Seguridad IS-27 Rev.1 [5] sobre criterios generales de diseño (trasladada del apéndice A del 10CFR50 [2]), la Instrucción de Seguridad IS-26 Rev.0 [23] sobre requisitos básicos de seguridad nuclear, el apéndice B del 10CFR50 [3] sobre criterios de garantía de calidad y la guía reguladora RG-1.100 Rev.1/2 [7] [8] sobre calificación sísmica de equipos. Se define el marco regulatorio de aplicación para ambas CCNN y acorde a la RG-1.29 Rev.3/4 [6] sobre clasificación de diseño sísmico, se procede con la clasificación de equipos y componentes que deben ser diseñados como categoría sísmica 1 para soportar los efectos del terremoto base de diseño (SSE). La calificación sísmica de equipos y componentes exige que todos aquellos que estén relacionados con la seguridad, diseñados como categoría sísmica 1, deben permanecer funcionales ante el máximo movimiento vibratorio del suelo provocado por el SSE, con objeto de: asegurar la integridad de la barrera de presión del refrigerante del reactor, ser capaces de parar el reactor manteniéndolo en condición de parada segura e impedir o mitigar las consecuencias de accidentes que pudieran causar exposiciones a dosis de radiación en el exterior de la central, superiores a las indicadas en el 10CFR100 “Reactor Site Criteria” [1]. La calificación sísmica se lleva a cabo mediante análisis, ensayos, o combinación de ambos según se establece en la norma principal de calificación sísmica IEEE 344 [9] avalada por la RG-1.100 Rev.1/2 [7] [8]. El objetivo es evidenciar que un equipo o componente puede realizar su función de seguridad bajo condiciones de un evento base de diseño (DBE). Por último, se integra en la calificación sísmica el concepto de margen sísmico establecido por NUREG-1407 “Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities” [10] y desarrollado por EPRI en documento NP-6041-SLR1 “A Methodology for Assessment of Nuclear Power Plant Seismic Margin” [11]. El objetivo es el de garantizar el funcionamiento o integridad de equipos y componentes ante solicitaciones sísmicas que van más allá a las consideradas en el diseño original de la planta.

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  • image/svg+xml art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos Open Access logo, converted into svg, designed by PLoS. This version with transparent background. http://commons.wikimedia.org/wiki/File:Open_Access_logo_PLoS_white.svg art designer at PLoS, modified by Wikipedia users Nina, Beao, JakobVoss, and AnonMoos http://www.plos.org/
    Authors: Martin, Guillaume; Coquelet-Pascal, C.;

    The symbiotic equilibrium between 1.51 GWe breeder SFR (Sodium Fast Reactors) and 1.6 GWe EPR$^{TM}$ (European Pressurized water Reactors) is studied. EPR$^{TM}$ are only supplied with MOX (Mixed OXide) fuel to avoid the use of natural uranium. The equilibrium is studied by considering the flows of plutonium. Its isotopic composition is here described by a single real number referred to as the Pu grade. Plutonium flows through both reactor types are characterized by using linear functions of the Pu grade in new fuels. These functions have been determined by fitting data from a former scenario study carried out with the COSI6 simulation software. Two different reprocessing strategies are considered. With joint reprocessing of all spent fuels, total and fissile plutonium flows balance for a unique fraction x of EPR$^{TM}$ in the fleet, equal to 0.2547. This x value is consistent with the results reported in the former scenario study mentioned above. When EPR$^{TM}$ spent fuels are used in priority to supply SFR (distinct reprocessing), x reaches 0.2582 at most. COSI6 simulations have been performed to further assess these results. The EPR$^{TM}$ fraction in the fleet at symbiotic equilibrium barely depends on the applied reprocessing strategy, so that the more flexible joint reprocessing constitutes the reference option in that case. International audience

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    Annals of Nuclear Energy
    Article . 2017 . Peer-reviewed
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      Annals of Nuclear Energy
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  • Authors: Pradel, Nicolas;

    International audience; If existing international rules in the field of nuclear energy will probably not be modified in a substantive way in the coming years, some weaknesses related to their implementation and the development of new fission and fusion technologies will involve limited adaptation or, at least, a better implementation of these rules. This predicable absence of a revolution of international nuclear law shows the States willingness to maintain a flexible system of world governance of nuclear energy.; Si les règles existantes du droit international de l'énergie nucléaire semblent ne pas devoir être radicalement modifiées dans les années à venir, il n'en demeure pas moins que certaines faiblesses dans leur mise en oeuvre ainsi que le développement de nouvelles technologies de fission et de fusion nucléaires appellent des adaptations limitées, ou à tout le moins, une meilleure application de celles-ci. Cette absence prévisible d'une révolution du droit nucléaire international manifeste la volonté des États de maintenir un système souple de gouvernance mondiale de l'énergie nucléaire.

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  • image/svg+xml Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao Closed Access logo, derived from PLoS Open Access logo. This version with transparent background. http://commons.wikimedia.org/wiki/File:Closed_Access_logo_transparent.svg Jakob Voss, based on art designer at PLoS, modified by Wikipedia users Nina and Beao
    Authors: Casamor Vidal, Max; Avramova, Maria; Reventós Puigjaner, Francesc Josep; Freixa Terradas, Jordi;

    Several TH-TH code coupling methods are used in the nuclear industry to model the core thermal–hydraulic conditions and the system behaviour. In some cases, the boundary conditions obtained by system codes are applied to sub-channel codes by table (off-line coupling). Even though this approach is in general considered valid, some boundary parameters will present inconsistencies. Alternatively, system and sub-channel codes are coupled using different coupling methods (semi-implicit coupling). Recent studies have shown a strong influence of the bound- ary conditions uncertainty on the sub-channel code results. The present study aims to evaluate the differences produced by the coupling methods by performing a best-estimate plus uncertainties (BEPU) comparison to the following cases: a complete loss of forced flow and a pressurizer relief valve opening. Results show that BEPU analysis presents good agreement with some discrepancies that can be explained and correlated to the boundary conditions deviations between codes. Peer Reviewed

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    Annals of Nuclear Energy
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      Annals of Nuclear Energy
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    Authors: John J. Laureto; Joshua M. Pearce;

    International audience; Quantification of nuclear liability insurance is difficult without arbitrary liability caps; however, post-mortem calculations can be used to calculate insurance costs. This study analyzes the Fukushima (Daiichi) nuclear power plant disaster to quantify the cost per unit electricity ($/kWh) of nuclear energy from the lifetime of the plant after accounting for the true cost of the liability needed to cover the damages from the nuclear disaster determined from news reports. These costs are then compared to the cost of electricity currently paid by Japanese consumers, and then are aggregated to determine the indirect subsidy for nuclear power providers in both Japan and the USA. The results show that the reported costs of the Fukushima nuclear disaster are $20–525 billion, which results in a real insurance cost from the lifetime of electricity produced at the plants between $0.22–5.78/kWh. These values are far higher than the current insurance costs by Japanese law of $0.01/kWh and even the total costs consumers pay for electricity. Although the spread in the input costs is large and the reported metrics are incomplete, the nuclear insurance subsidy is clearly substantial in Japan and in the USA. Ideally, energy sources should be economically sustainable without the need for a government insurance subsidy. For the electricity market to function effectively and efficiently in all other countries using nuclear power, the insurance costs should be reported accurately and included in nuclear electricity costs without arbitrary government liability caps.

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    Authors: Torné Capilla, Eduard;

    En 2019 la energía nuclear fue la segunda fuente de generación de energía eléctrica en España con un 22,6% de la producción. La energía nuclear se produce mediante una reacción nuclear que a su vez genera materiales radiactivos, y es de alta importancia estudiar la seguridad de todos los elementos y procesos que intervienen, para evitar que dichos materiales radiactivos puedan afectar al medio ambiente. Una de las metodologías utilizadas para mejorar la seguridad de operaciones es el Análisis Probabilista de Seguridad (APS), a fin de identificar secuencias de accidentes que puedan afectar negativamente y estimar su frecuencia de ocurrencia para minimizar el riesgo. En las centrales nucleares es tan importante el APS realizado con frecuencia, cómo el contraste de los resultados obtenidos y los proporcionados por Bases de Datos Genéricas (BDG) de referencia, en este caso la española. En este trabajo se compararán los valores del parámetro de fiabilidad de ambas bases de datos, la propia de la central nuclear estudiada y la genérica española, con objetivo de identificar y justificar las diferencias más significativas. Debido a la gran diversidad de elementos presente en una central nuclear, y el gran alcance del APS, se realiza inicialmente un estudio entorno a la metodología APS. De este modo, se podrán comprobar los valores de la central a partir de la metodología APS utilizada, así como los tratamientos, distribuciones y agrupaciones utilizadas en cada caso a partir de los criterios que se definen en función del modo de operación. Una vez revisados los valores numéricos se analizarán todos los fallos de cada grupo, ya que son los responsables de aumentar o disminuir el valor del parámetro de fiabilidad o probabilidad de fallo. El criterio utilizado para evaluar si el fallo pertenece al grupo asociado son los límites de fallo en función de cada componente y del modo de trabajo. Se buscan fallos clasificados en componentes con causas externas a éste, modificando su valor de fiabilidad. A la vez, se clasifican las causas de fallo más comunes para grupos con muchos fallos. Una vez identificados los casos a reclasificar, se calculan de nuevo los valores del parámetro de fiabilidad. A partir de los valores de fiabilidad iniciales y los modificados, se estudian cuáles son los componentes con mayor divergencia respecto la Base de Datos Genérica, buscando casos representativos para proponer su revisión. Se profundiza para identificar elementos en modos de trabajo concretos. Finalmente se relacionan las observaciones realizadas durante el análisis de los fallos y los grupos con mayor divergencia a la base de datos genérica para justificar sus diferencias. Es posible realizar el proyecto gracias al convenio de investigación entre una central nuclear y la Sección de Ingeniería Nuclear de la Universidad Politécnica de Cataluña (UPC).

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    Authors: Elgezabal Garmendia, Imanol;
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    Authors: Albaladejo Castelló, Eduard;

    This project is based on the revision and update proposal of document PA.IV.202 Rev.2 “Calculation Manual of the Performance Indicator of Mitigation Systems (MSPI)”. This document is used by the Spanish Nuclear Safety Council (CSN) to verify the performance indicators of nuclear power plants within the framework of the Integrated Plant Supervision System (SISC). This CSN procedure is regularly updated to include news and / or changes in its procedures. During the project, an exhaustive search was made for the changes or new interpretations that have appeared in the meetings of the Reactor Oversight Process (ROP) of the American nuclear regulator Nuclear Regulatory Commission (NRC). In accordance with these periodic meetings, news and changes are published in the regulations of NEI 99-02 Rev. 7, which is the document accepted by the US regulator as a guide for calculating the operating indicators of American nuclear power plants and that it is the basic information for the update of PA.IV.202. On the other hand, the frequently asked questions(FAQs) relevant to the MSPI indicator from plant licensees to the NRC have been compiled. These are issues raised to the regulator due to events that have occurred in nuclear power plants that call into question some aspects of the guidelines, such as the calculation procedure for an indicator. Therefore, through these frequently asked questions, procedures improvements or changes to NEI 99-02 are proposed to correct potential errors that the NRC has to approve before implementation. Subsequently, the FAQs are incorporated into document NEI-99-02. Once all the necessary information from NEI 99-02, the ROP meetings and the FAQs have been collected, a list has been made with all the news and changes relevant to the MSPI indicator. In addition, information has been included regarding the history of nuclear energy in Spain, regulations used by the CSN and on the SISC. Finally, the changes from the previously listed American case have been transferred to the Spanish case. The relevant changes for the MSPI indicator have been selected and adapted to update PA.IV.202 Rev.2 by rewriting its procedures. Also, it is important to say that the procedures have been updated in Spanish since it is a Spanish document. Therefore, the practical part of this project (tables 4, 5 and 6 in section 6) are written in the same language as PA.IV.202 Rev. 2.

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  • Authors: Finon, Dominique;

    In this paper we analyze the recent propositions to reorganize the French industry of reactors in view to increase its efficiency on the export markets. Based on a critic of the choices of reactor technologies offered to export market, the Roussely report published on June 2010 recommends to crown the French electricity utility as the leader of a so-called "French team" and to let him free to negotiate the sale of reactor of any technology that it would prefer as a Gen-2 reactor for example, and to place the French nuclear reactor constructor in a position of sub-contractor. The government has not followed this recommendation rightly. Based on an analysis of the changing world market of reactors, we defuse the criticism addressed to Areva on his choice, as well as the recommendation to open the present catalog of reactors to other models. The analysis leads to underline the importance of Areva's technological and industrial resources and the limited advantages of the EDF's skills in matter of architect-engineering and nuclear operation for winning export contracts. At the end of the day the mercantile approach which motivates the promoters of this tentative reform for competing with entrants prosing low cost nuclear reactors has been disapproved by the government, and that before the Fukushima accidents. We conclude by observing that only a flexible coordination between French industrial players would be useful for improving export performances of the French nuclear industry. On analyse ici les propositions récentes de réorganisation de l'industrie française des réacteurs en vue d'accroître son efficacité à l'exportation. A partir d'une critique des choix de technologies offerts à l'export, le rapport Roussely recommandait de placer l'électricien national en chef de file libre de négocier la vente des réacteurs de son choix (dont des réacteurs Gen2) et de faire du constructeur français le sous-traitant du premier. Le gouvernement n'a pas suivi ces recommandations à juste titre. A partir d'une analyse du marché mondial des réacteurs en mutation, on relativise les critiques adressées à Areva sur ses choix ainsi que l'intérêt d'élargir le catalogue de réacteurs. Cette analyse permet de souligner l'importance des ressources technologiques et industrielles d'Areva dans la concurrence et l'avantage tout relatif des compétences d'architecte-ensemblier et d'exploitant de l'électricien national dans la conquête de marché à l'exportation. Au bout du compte, la démarche mercantile qui motivait les promoteurs de cette réforme en ambitionnant de concurrencer les entrants avec du nucléaire low cost a été désavouée par le gouvernement et ce avant même l'accident de Fukushima. Un peu plus de coordination à l'export serait juste nécessaire.

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    Authors: Paul W., Thurner; Brouard, Sylvain; Martin, Dolezal; Guinaudeau, Isabelle; +2 Authors

    This chapter provides an account of the contestation of nuclear energy in Western Europe and beyond. It presents a new compilation of comparative public opinion data on nuclear energy, original data on protest behaviour directed against nuclear energy, and a systematic account of the development of Green parties. The focus is on the covariation of these factors with the behaviour of the established political parties and system properties (Kitschelt’s ‘openness’). The main function of the chapter is to show the relative strength of the ‘natural enemies’ of nuclear energy—concerned citizens, protest movements, and Green parties—in the countries covered by case studies (and beyond, where possible) and to understand how they interact. The chapter argues that neither public opinion critical to nuclear energy nor sizeable protest behaviour is sufficient to introduce anti-nuclear policy change.

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    Oskar Bordeaux
    Part of book or chapter of book . 2017
    Data sources: Oskar Bordeaux
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    Authors: Mendoza Sancho, Victor;

    El presente trabajo final de máster se realiza con objeto de establecer una guía técnica en la Asociación Nuclear Ascó - Vandellós II, AIE para llevar a cabo la calificación sísmica de equipos y componentes relacionados con la seguridad, de categoría sísmica 1, en cumplimiento con las bases de licencia de las centrales nucleares (CCNN) de Ascó y Vandellós II. La calificación sísmica se desarrolla en base a requisitos normativos de distinto nivel, de ámbito nacional e internacional, a aplicar en instalaciones nucleares, donde destaca la Instrucción de Seguridad IS-27 Rev.1 [5] sobre criterios generales de diseño (trasladada del apéndice A del 10CFR50 [2]), la Instrucción de Seguridad IS-26 Rev.0 [23] sobre requisitos básicos de seguridad nuclear, el apéndice B del 10CFR50 [3] sobre criterios de garantía de calidad y la guía reguladora RG-1.100 Rev.1/2 [7] [8] sobre calificación sísmica de equipos. Se define el marco regulatorio de aplicación para ambas CCNN y acorde a la RG-1.29 Rev.3/4 [6] sobre clasificación de diseño sísmico, se procede con la clasificación de equipos y componentes que deben ser diseñados como categoría sísmica 1 para soportar los efectos del terremoto base de diseño (SSE). La calificación sísmica de equipos y componentes exige que todos aquellos que estén relacionados con la seguridad, diseñados como categoría sísmica 1, deben permanecer funcionales ante el máximo movimiento vibratorio del suelo provocado por el SSE, con objeto de: asegurar la integridad de la barrera de presión del refrigerante del reactor, ser capaces de parar el reactor manteniéndolo en condición de parada segura e impedir o mitigar las consecuencias de accidentes que pudieran causar exposiciones a dosis de radiación en el exterior de la central, superiores a las indicadas en el 10CFR100 “Reactor Site Criteria” [1]. La calificación sísmica se lleva a cabo mediante análisis, ensayos, o combinación de ambos según se establece en la norma principal de calificación sísmica IEEE 344 [9] avalada por la RG-1.100 Rev.1/2 [7] [8]. El objetivo es evidenciar que un equipo o componente puede realizar su función de seguridad bajo condiciones de un evento base de diseño (DBE). Por último, se integra en la calificación sísmica el concepto de margen sísmico establecido por NUREG-1407 “Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities” [10] y desarrollado por EPRI en documento NP-6041-SLR1 “A Methodology for Assessment of Nuclear Power Plant Seismic Margin” [11]. El objetivo es el de garantizar el funcionamiento o integridad de equipos y componentes ante solicitaciones sísmicas que van más allá a las consideradas en el diseño original de la planta.

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    Authors: Martin, Guillaume; Coquelet-Pascal, C.;

    The symbiotic equilibrium between 1.51 GWe breeder SFR (Sodium Fast Reactors) and 1.6 GWe EPR$^{TM}$ (European Pressurized water Reactors) is studied. EPR$^{TM}$ are only supplied with MOX (Mixed OXide) fuel to avoid the use of natural uranium. The equilibrium is studied by considering the flows of plutonium. Its isotopic composition is here described by a single real number referred to as the Pu grade. Plutonium flows through both reactor types are characterized by using linear functions of the Pu grade in new fuels. These functions have been determined by fitting data from a former scenario study carried out with the COSI6 simulation software. Two different reprocessing strategies are considered. With joint reprocessing of all spent fuels, total and fissile plutonium flows balance for a unique fraction x of EPR$^{TM}$ in the fleet, equal to 0.2547. This x value is consistent with the results reported in the former scenario study mentioned above. When EPR$^{TM}$ spent fuels are used in priority to supply SFR (distinct reprocessing), x reaches 0.2582 at most. COSI6 simulations have been performed to further assess these results. The EPR$^{TM}$ fraction in the fleet at symbiotic equilibrium barely depends on the applied reprocessing strategy, so that the more flexible joint reprocessing constitutes the reference option in that case. International audience

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    Annals of Nuclear Energy
    Article . 2017 . Peer-reviewed
    License: Elsevier TDM
    Data sources: Crossref
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      Annals of Nuclear Energy
      Article . 2017 . Peer-reviewed
      License: Elsevier TDM
      Data sources: Crossref
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  • Authors: Pradel, Nicolas;

    International audience; If existing international rules in the field of nuclear energy will probably not be modified in a substantive way in the coming years, some weaknesses related to their implementation and the development of new fission and fusion technologies will involve limited adaptation or, at least, a better implementation of these rules. This predicable absence of a revolution of international nuclear law shows the States willingness to maintain a flexible system of world governance of nuclear energy.; Si les règles existantes du droit international de l'énergie nucléaire semblent ne pas devoir être radicalement modifiées dans les années à venir, il n'en demeure pas moins que certaines faiblesses dans leur mise en oeuvre ainsi que le développement de nouvelles technologies de fission et de fusion nucléaires appellent des adaptations limitées, ou à tout le moins, une meilleure application de celles-ci. Cette absence prévisible d'une révolution du droit nucléaire international manifeste la volonté des États de maintenir un système souple de gouvernance mondiale de l'énergie nucléaire.

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